US5406601A - Transport and storage cask for spent nuclear fuel - Google Patents

Transport and storage cask for spent nuclear fuel Download PDF

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Publication number
US5406601A
US5406601A US08/236,308 US23630894A US5406601A US 5406601 A US5406601 A US 5406601A US 23630894 A US23630894 A US 23630894A US 5406601 A US5406601 A US 5406601A
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United States
Prior art keywords
basket
cask
cask body
plates
open end
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Expired - Fee Related
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US08/236,308
Inventor
James R. Hinderer
Daniel L. Mensink
Thomas E. Rollman
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BWX Technologies Inc
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Babcock and Wilcox Co
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Priority to US08/236,308 priority Critical patent/US5406601A/en
Assigned to BABCOCK & WILCOX COMPANY, THE reassignment BABCOCK & WILCOX COMPANY, THE ASSIGNMENT OF ASSIGNORS INTEREST (SEE DOCUMENT FOR DETAILS). Assignors: HINDERER, JAMEES R., MENSINK, DANIEL L., ROLLMAN, THOMAS E.
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Publication of US5406601A publication Critical patent/US5406601A/en
Assigned to BWX TECHNOLOGIES, INC. reassignment BWX TECHNOLOGIES, INC. ASSIGNMENT OF ASSIGNORS INTEREST (SEE DOCUMENT FOR DETAILS). Assignors: BABCOCK & WILCOX COMPANY, THE
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00Transportable or portable shielded containers
    • G21F5/005Containers for solid radioactive wastes, e.g. for ultimate disposal
    • G21F5/008Containers for fuel elements

Definitions

  • the invention is generally related to the transport and storage of radioactive material and particularly to a cask that can be used for transporting or storing spent nuclear fuel.
  • Nuclear reactors require periodic replacement of the nuclear fuel. Fuel removed from reactors in naval vessels and some land based commercial reactors must be transported to a storage site. In some instances, there may be storage room at the site of the land based reactor.
  • the United States Nuclear Regulatory Commission sets standards that must be met for casks that are used to transport or store spent nuclear fuel. Due to the different conditions that may be encountered during transport and static storage, separate standards are set for transport casks and for storage casks. These standards are respectively set forth in 10 CFR 71 and 10 CFR 72. Shipping casks must be able to withstand shock loads during transport while storage casks must be able to withstand temperature transients such as a fire external to the cask without transmitting additional heat to the inside of the cask.
  • the present invention addresses the above problem in a straightforward manner.
  • a cask that can be used for both transport and storage of spent nuclear fuel.
  • the cask body and basket are designed such that there is a gap between the cask body and basket.
  • the basket is formed from multiple layers of rowed plates that cooperate with the cask body to provide the required radiation shielding, thermal, and structural requirements of 10 CFR 71 and 10 CFR 72.
  • the plates have complementary shapes and partial hex grooves machined therein such that complete channels for the fuel cells are formed when the plates are mated for insertion into the cask body.
  • the plates have narrowed diameter sections and are held together by bands around the circumference of the plates at these sections.
  • Locating keys received in grooves between the plates extend the entire axial length of the basket to hold the plates in alignment during assembly and to block radiation leakage across the vertical gaps between the plates.
  • Centering keys are provided at the upper and lower ends of the basket and cask body to provide a consistent gap between the basket and cask body. The gap expands during a fire due to thermal expansion of the cask body prior to thermal expansion of the basket and thus does not allow conduction of the external heat into the basket and fuel during an external transient temperature rise.
  • FIG. 1 is a longitudinal section view of the invention.
  • FIG. 2 is a perspective view of the basket of the invention.
  • Transport and storage cask 10 is generally comprised of cask body 12, and basket 14.
  • Cask body 12 is formed from stainless steel in the preferred embodiment. As seen in FIG. 1, cask body 12 is closed at one end and provided with suitable shield and seal means at the opposite end. The interior diameter of the upper end of cask body 12 is slightly larger than the remainder of the interior of cask body 12 to receive shield plug 16. This helps to prevent radiation leakage through the upper end. Shear ring segments 18 are positioned on top of shield plug 16 and are received in a notch 20 provided around the inner circumference of cask body 12. Shear ring segments 18 prevent operating and accident loads from being transferred to inner lid 22 which is positioned immediately above shield plug 16. Inner lid 22 is provided with a groove around its lower end necessary to fit around shear ring segments 18.
  • Inner lid 22 may be seal welded to the inner circumference of cask body 12 as indicated at numeral 24.
  • Outer lid 26 is fastened around its circumference to cask body 12 by bolts or studs 28.
  • a replaceable metal O-ring 30 may be placed between outer lid 26 and the end of cask body 12 to provide an outer seal.
  • Lifting bales 32 are provided as necessary on the exterior of cask body 12.
  • Basket 14 is formed from multiple layers of rowed carbon steel plates 34.
  • Plates 34 have complementary shapes and partial hex grooves machined therein such that complete channels 36 for the fuel cells are formed when plates 34 are mated for insertion into cask body 12.
  • Channels 36 are illustrated as being hexagonal but may be of any suitable shape depending on the material to be transported or stored.
  • Plates 34 have a narrowed diameter 38 at each end and at intervals spaced apart along their length.
  • Bands 40 are attached to each other by bolts 41 around plates 34 at each narrowed circumference point 38 to hold plates 34 in their assembled positions.
  • the flat mating surfaces of plates 34 are machined to provide a close fit to prevent radiation leakage between plates 34.
  • plates 34 may also each be provided with complementary grooves along their length to form a channel 42 between each plate sized to receive a locating key 44 that extends the full length of the plates.
  • Each locating key 44 serves the dual purpose of holding the plates in alignment during assembly and blocking radiation from leaking between the mating surfaces at the plate junctions.
  • Means for centering basket 14 in cask body 12 to maintain a steady state gap between the interior of cask body 12 and basket 14 are provided on cask body 12 and basket 14 in the form of centering keys 46.
  • female key ways are provided at the lower end of basket that are designed to receive male keys on the inside lower end of cask body 12 while male keys are provided at the upper end of basket 14 and female key ways are provided at the upper end of cask body 12.
  • the centering keys at the lower end of cask body 12 and basket 14 are preferably sized such that they engage basket 14 during installation in cask body 12 before the centering keys at the upper end engage. This provides for automatic location of the upper centering keys.
  • spent nuclear fuel is loaded into fuel cell channels 36 and shield plug 16, inner lid 22, and outer lid 26 are installed. Basket 14 and cask body 12 both undergo thermal expansion due to thermal radiation from the spent fuel that results in the gap between them remaining constant.
  • cask body 12 will absorb heat from the fire and undergo thermal expansion.
  • little or none of the absorbed heat will be transferred across the gap and the gap will enlarge due to thermal expansion of cask body 12.
  • the elevated temperature of cask body 12 from the fire precludes radiation of waste heat from the spent fuel, it has been determined that the peak fuel temperature will not occur until over twelve hours after the onset of the fire transient.
  • the present invention thus provides a storage cask for spent nuclear fuel that is capable of withstanding normal operating and accident loads during transportation and normally expected fire transients.

Abstract

A transport and storage cask for spent nuclear fuel. A cask body having one open end receives a basket in such a manner so as to maintain a steady state gap between the cask body and basket. Centering keys on the cask body and basket provide the centering function. For ease of manufacture, the basket is formed from multiple layers of rowed carbon steel plates that have complementary grooves in their mating surfaces to form fuel cell channels when the plates are assembled together. Bands are attached together around the plates at narrowed diameter portions on the plates to hold the plates in their assembled position. The gap between the basket and cask body allows the cask to withstand a fire transient without transmitting heat from the fire into the basket.

Description

BACKGROUND OF THE INVENTION
1. Field of the Invention
The invention is generally related to the transport and storage of radioactive material and particularly to a cask that can be used for transporting or storing spent nuclear fuel.
2. General Background
Nuclear reactors require periodic replacement of the nuclear fuel. Fuel removed from reactors in naval vessels and some land based commercial reactors must be transported to a storage site. In some instances, there may be storage room at the site of the land based reactor. The United States Nuclear Regulatory Commission sets standards that must be met for casks that are used to transport or store spent nuclear fuel. Due to the different conditions that may be encountered during transport and static storage, separate standards are set for transport casks and for storage casks. These standards are respectively set forth in 10 CFR 71 and 10 CFR 72. Shipping casks must be able to withstand shock loads during transport while storage casks must be able to withstand temperature transients such as a fire external to the cask without transmitting additional heat to the inside of the cask. As a result, it is common to have separate casks for transport and storage. This presents the need for additional work in the form of transferring the fuel from one cask to another once the shipment has arrived at the storage site. If there is not an immediate need for reuse of the transport cask, then the transport cask which has a radioactive interior after use must also be stored until it is needed again.
SUMMARY OF THE INVENTION
The present invention addresses the above problem in a straightforward manner. What is provided is a cask that can be used for both transport and storage of spent nuclear fuel. The cask body and basket are designed such that there is a gap between the cask body and basket. The basket is formed from multiple layers of rowed plates that cooperate with the cask body to provide the required radiation shielding, thermal, and structural requirements of 10 CFR 71 and 10 CFR 72. The plates have complementary shapes and partial hex grooves machined therein such that complete channels for the fuel cells are formed when the plates are mated for insertion into the cask body. The plates have narrowed diameter sections and are held together by bands around the circumference of the plates at these sections. Locating keys received in grooves between the plates extend the entire axial length of the basket to hold the plates in alignment during assembly and to block radiation leakage across the vertical gaps between the plates. Centering keys are provided at the upper and lower ends of the basket and cask body to provide a consistent gap between the basket and cask body. The gap expands during a fire due to thermal expansion of the cask body prior to thermal expansion of the basket and thus does not allow conduction of the external heat into the basket and fuel during an external transient temperature rise.
BRIEF DESCRIPTION OF THE DRAWINGS
For a further understanding of the nature and objects of the present invention reference should be had to the following description, taken in conjunction with the accompanying drawings, in which like parts are given like reference numerals, and wherein:
FIG. 1 is a longitudinal section view of the invention.
FIG. 2 is a perspective view of the basket of the invention.
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENT
Referring to the drawings, it is seen in FIG. 1 that the invention is generally indicated by the numeral 10. Transport and storage cask 10 is generally comprised of cask body 12, and basket 14.
Cask body 12 is formed from stainless steel in the preferred embodiment. As seen in FIG. 1, cask body 12 is closed at one end and provided with suitable shield and seal means at the opposite end. The interior diameter of the upper end of cask body 12 is slightly larger than the remainder of the interior of cask body 12 to receive shield plug 16. This helps to prevent radiation leakage through the upper end. Shear ring segments 18 are positioned on top of shield plug 16 and are received in a notch 20 provided around the inner circumference of cask body 12. Shear ring segments 18 prevent operating and accident loads from being transferred to inner lid 22 which is positioned immediately above shield plug 16. Inner lid 22 is provided with a groove around its lower end necessary to fit around shear ring segments 18. Inner lid 22 may be seal welded to the inner circumference of cask body 12 as indicated at numeral 24. Outer lid 26 is fastened around its circumference to cask body 12 by bolts or studs 28. A replaceable metal O-ring 30 may be placed between outer lid 26 and the end of cask body 12 to provide an outer seal. Lifting bales 32 are provided as necessary on the exterior of cask body 12.
Basket 14, best seen in FIG. 2, is formed from multiple layers of rowed carbon steel plates 34. Plates 34 have complementary shapes and partial hex grooves machined therein such that complete channels 36 for the fuel cells are formed when plates 34 are mated for insertion into cask body 12. Channels 36 are illustrated as being hexagonal but may be of any suitable shape depending on the material to be transported or stored. Plates 34 have a narrowed diameter 38 at each end and at intervals spaced apart along their length. Bands 40 are attached to each other by bolts 41 around plates 34 at each narrowed circumference point 38 to hold plates 34 in their assembled positions. The flat mating surfaces of plates 34 are machined to provide a close fit to prevent radiation leakage between plates 34. However, plates 34 may also each be provided with complementary grooves along their length to form a channel 42 between each plate sized to receive a locating key 44 that extends the full length of the plates. Each locating key 44 serves the dual purpose of holding the plates in alignment during assembly and blocking radiation from leaking between the mating surfaces at the plate junctions.
Means for centering basket 14 in cask body 12 to maintain a steady state gap between the interior of cask body 12 and basket 14 are provided on cask body 12 and basket 14 in the form of centering keys 46. In the preferred embodiment, female key ways are provided at the lower end of basket that are designed to receive male keys on the inside lower end of cask body 12 while male keys are provided at the upper end of basket 14 and female key ways are provided at the upper end of cask body 12. The centering keys at the lower end of cask body 12 and basket 14 are preferably sized such that they engage basket 14 during installation in cask body 12 before the centering keys at the upper end engage. This provides for automatic location of the upper centering keys.
In use, spent nuclear fuel is loaded into fuel cell channels 36 and shield plug 16, inner lid 22, and outer lid 26 are installed. Basket 14 and cask body 12 both undergo thermal expansion due to thermal radiation from the spent fuel that results in the gap between them remaining constant. During a fire transient, cask body 12 will absorb heat from the fire and undergo thermal expansion. However, due to the gap between cask body 12 and basket 14, little or none of the absorbed heat will be transferred across the gap and the gap will enlarge due to thermal expansion of cask body 12. Although the elevated temperature of cask body 12 from the fire precludes radiation of waste heat from the spent fuel, it has been determined that the peak fuel temperature will not occur until over twelve hours after the onset of the fire transient. The present invention thus provides a storage cask for spent nuclear fuel that is capable of withstanding normal operating and accident loads during transportation and normally expected fire transients.
Because many varying and differing embodiments may be made within the scope of the inventive concept herein taught and because many modifications may be made in the embodiment herein detailed in accordance with the descriptive requirement of the law, it is to be understood that the details herein are to be interpreted as illustrative and not in a limiting sense.

Claims (3)

What is claimed as invention is:
1. A transport and storage cask for spent nuclear fuel, comprising:
a. a cask body having one open end;
b. a basket formed from multiple layers of rowed plates that have complementary notches therein along the length of the plates such that the notches form fuel cell channels when the plates are assembled adjacent each other, said basket sized to be received in said cask body;
c. centering keys on said cask body and said basket that maintain a gap between the inner surface of said cask body and the outer surface of said basket; and
d. means for shielding and sealing the open end of said cask body.
2. The transport and storage cask of claim 1, further comprising locating keys that extend the length of said basket and are received in notches in the mating surfaces of the plates forming said basket.
3. The transport and storage cask of claim 1, wherein said means for shielding and sealing the open end of said cask body comprises:
a. a shield plug received in the open end immediately above said basket;
b. a shear ring installed in said cask body between said shield plug and the open end of said cask body;
c. an inner lid seal welded in said cask body between said shear ring and the open end of said cask body; and
d. an outer lid fastened to the open end of said cask body.
US08/236,308 1994-05-02 1994-05-02 Transport and storage cask for spent nuclear fuel Expired - Fee Related US5406601A (en)

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Cited By (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5633904A (en) * 1994-11-09 1997-05-27 Newport News Shipbuilding And Dry Dock Company Spent nuclear fuel (SNF) dry transfer system
US5898747A (en) * 1997-05-19 1999-04-27 Singh; Krishna P. Apparatus suitable for transporting and storing nuclear fuel rods and methods for using the apparatus
US20040011971A1 (en) * 1996-05-03 2004-01-22 British Nuclear Fuels Plc. Container for nuclear fuel transportation
US20050286674A1 (en) * 2004-06-29 2005-12-29 The Regents Of The University Of California Composite-wall radiation-shielded cask and method of assembly
US20060043320A1 (en) * 1996-05-03 2006-03-02 British Nuclear Fuels Plc Container for nuclear fuel transportation
US20060222139A1 (en) * 2005-03-29 2006-10-05 Nac International, Inc. Methods for demonstrating moderator exclusion for nuclear criticality safety
US20080137794A1 (en) * 2005-12-01 2008-06-12 Nac International, Inc. Systems and methods for loading and transferring spent nuclear fuel
US20090069621A1 (en) * 2006-10-11 2009-03-12 Singh Krishna P Method of removing radioactive materials from a submerged state and/or preparing spent nuclear fuel for dry storage
US20090304137A1 (en) * 2005-08-11 2009-12-10 Tn International Package Serving to Accommodate a Case Containing Radioactive
US8995604B2 (en) 2009-11-05 2015-03-31 Holtec International, Inc. System, method and apparatus for providing additional radiation shielding to high level radioactive materials
RU167950U1 (en) * 2016-06-21 2017-01-13 Федеральное государственное унитарное предприятие "Российский федеральный ядерный центр - Всероссийский научно-исследовательский институт технической физики имени академика Е.И. Забабахина" Container for transporting and / or storage of spent nuclear fuel
RU2611057C1 (en) * 2016-03-02 2017-02-21 Федеральное государственное унитарное предприятие "Российский Федеральный ядерный центр - Всероссийский научно-исследовательский институт экспериментальной физики" (ФГУП "РФЯЦ-ВНИИЭФ") Container for storage and transportation of spent fuel assemblies and case for their arrangement
JP2017078580A (en) * 2015-10-19 2017-04-27 株式会社神戸製鋼所 Radioactive material transportation storage container, and manufacturing method of radioactive material transportation storage container
WO2020197430A1 (en) * 2019-03-27 2020-10-01 Акционерное общество "Логистический центр ЯТЦ" (АО "ЛЦ ЯТЦ") Casing of container for transportation and storage of spent fuel assemblies
US11342091B2 (en) * 2004-03-18 2022-05-24 Holtec International Systems and methods for storing spent nuclear fuel

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3466445A (en) * 1967-10-06 1969-09-09 Atomic Energy Commission Container for radioactive fuel elements
US4292528A (en) * 1979-06-21 1981-09-29 The Carborundum Company Cask for radioactive material and method for preventing release of neutrons from radioactive material

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3466445A (en) * 1967-10-06 1969-09-09 Atomic Energy Commission Container for radioactive fuel elements
US4292528A (en) * 1979-06-21 1981-09-29 The Carborundum Company Cask for radioactive material and method for preventing release of neutrons from radioactive material

Cited By (25)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5633904A (en) * 1994-11-09 1997-05-27 Newport News Shipbuilding And Dry Dock Company Spent nuclear fuel (SNF) dry transfer system
US20110001066A1 (en) * 1996-05-03 2011-01-06 British Nuclear Fuels Plc, Container for nuclear fuel transportation
US20040011971A1 (en) * 1996-05-03 2004-01-22 British Nuclear Fuels Plc. Container for nuclear fuel transportation
US6770897B2 (en) 1996-05-03 2004-08-03 British Nuclear Fuels Plc Container for nuclear fuel transportation
US6825483B2 (en) 1996-05-03 2004-11-30 British Nuclear Fuels Plc Container for nuclear fuel transportation
US20060043320A1 (en) * 1996-05-03 2006-03-02 British Nuclear Fuels Plc Container for nuclear fuel transportation
US8049194B2 (en) 1996-05-03 2011-11-01 Uranium Asset Management Limited Container for nuclear fuel transportation
US5898747A (en) * 1997-05-19 1999-04-27 Singh; Krishna P. Apparatus suitable for transporting and storing nuclear fuel rods and methods for using the apparatus
US6064710A (en) * 1997-05-19 2000-05-16 Singh; Krishna P. Apparatus suitable for transporting and storing nuclear fuel rods and methods for using the apparatus
US11342091B2 (en) * 2004-03-18 2022-05-24 Holtec International Systems and methods for storing spent nuclear fuel
US20050286674A1 (en) * 2004-06-29 2005-12-29 The Regents Of The University Of California Composite-wall radiation-shielded cask and method of assembly
US20060222139A1 (en) * 2005-03-29 2006-10-05 Nac International, Inc. Methods for demonstrating moderator exclusion for nuclear criticality safety
US20090304137A1 (en) * 2005-08-11 2009-12-10 Tn International Package Serving to Accommodate a Case Containing Radioactive
US8804895B2 (en) * 2005-08-11 2014-08-12 Tn International Cask intended to receive a canister containing radioactive material, and transfer method for said canister
US20080137794A1 (en) * 2005-12-01 2008-06-12 Nac International, Inc. Systems and methods for loading and transferring spent nuclear fuel
US8067659B2 (en) 2006-10-11 2011-11-29 Holtec International, Inc. Method of removing radioactive materials from a submerged state and/or preparing spent nuclear fuel for dry storage
US8415521B2 (en) 2006-10-11 2013-04-09 Holtec International, Inc. Apparatus for providing additional radiation shielding to a container holding radioactive materials, and method of using the same to handle and/or process radioactive materials
US7994380B2 (en) 2006-10-11 2011-08-09 Holtec International, Inc. Apparatus for transporting and/or storing radioactive materials having a jacket adapted to facilitate thermosiphon fluid flow
US20090069621A1 (en) * 2006-10-11 2009-03-12 Singh Krishna P Method of removing radioactive materials from a submerged state and/or preparing spent nuclear fuel for dry storage
US8995604B2 (en) 2009-11-05 2015-03-31 Holtec International, Inc. System, method and apparatus for providing additional radiation shielding to high level radioactive materials
US9208914B2 (en) 2009-11-05 2015-12-08 Holtec International System, method and apparatus for providing additional radiation shielding to high level radioactive materials
JP2017078580A (en) * 2015-10-19 2017-04-27 株式会社神戸製鋼所 Radioactive material transportation storage container, and manufacturing method of radioactive material transportation storage container
RU2611057C1 (en) * 2016-03-02 2017-02-21 Федеральное государственное унитарное предприятие "Российский Федеральный ядерный центр - Всероссийский научно-исследовательский институт экспериментальной физики" (ФГУП "РФЯЦ-ВНИИЭФ") Container for storage and transportation of spent fuel assemblies and case for their arrangement
RU167950U1 (en) * 2016-06-21 2017-01-13 Федеральное государственное унитарное предприятие "Российский федеральный ядерный центр - Всероссийский научно-исследовательский институт технической физики имени академика Е.И. Забабахина" Container for transporting and / or storage of spent nuclear fuel
WO2020197430A1 (en) * 2019-03-27 2020-10-01 Акционерное общество "Логистический центр ЯТЦ" (АО "ЛЦ ЯТЦ") Casing of container for transportation and storage of spent fuel assemblies

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